ML19329A697
| ML19329A697 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/17/1973 |
| From: | Schwencer A US ATOMIC ENERGY COMMISSION (AEC) |
| To: | James Keppler US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8001090679 | |
| Download: ML19329A697 (4) | |
Text
'
~
\\
Docket No. 50-269 J43 17573 J. G. Keppler, Chief, Reactor Testing and Operations Branch, RO OCONEE CORE FLOW EY-PASS VERIFICATION B&W has recalculated the core by-pass flow for Oconee Unit i using the present internals as built configuration nnd tolerances and found the
[
leakage flow calculation to be 50% below the original design allowance.
Dulre plans to include this information in its next application amendment.
j Since neither of the options discussed in the September 2, 1970 Report No. 2 to the ACRS are technically feasible at this time, we will accept this information when formally submitted as satisfying the requirement j
mentioned in the ACRS report.
Enclosed is a copy of a Duke internal note dated January 12, 1973, trans-mitting the B&W information to J. E. Smith, Superintendent, Oconee Nuclear Station.
Original Signed by Albert SchwCDC*f A. Schwencer, Chief Pressurir.ed Water Reactors Branch No. 4 Directorate of Licensing
Enclosure:
Duke note dtd 1/12/73 cc:
R. C. DeToung V. Stello I. A. Peltier DISTRIBUTION Docket PWR-4 Reading RP Reading ASchwencer L:PWR-4 L:PRR-4 r f M-f omer >
IAPeltier:emp ASekvencer
$URNAME>
1/
/73 1/r/'./73 DATE >.
..t.......
Form AEC-31s (Rev. 9-53) AECM 0240
- c. s. covenmuorT FamTmG OFFICE :1970 0 40s.344 800109 b7f A
January 12, 1973 Mr. J. E. Smith, Supt.
Oconee Nuclear Station Oconee Nuclear Station
Subject:
AEc/ao Outstanding Item 16.D ith AEC/R0 Please find attached for your information, and to share w1973 letter from upon clieir next visit, a copy of a January 4,This letter discuss dimensions and B&W has recalculated-the bypass flow using as built Straub.
he FSAR values.
. determined that the flow is within t h the AEC.
This information is sufficient to resolve this item wit
/' x K. S. Canady e
KSC:jv Attachment Mr.. P. H. Barton cc:
G I
O o
\\
t 9
v
- BEbCOCk & WilCOX eo ercenerauonouision P O. Box 1260, Lyncnburg, Va. 245C5 January 4,'1973.
Telenone:(703) 384-5111 -
B73-5 Mr. P. H. Barton Duke Power Company P. O. Box ~2178 7
Charlotte, N. C.
28201 Attention: Mr. K. S. Canady Shbject: ^ Oconee 1 R-40000 Outstanding Compliance Items 16.D
DearJfr.,
Barton:
i i
Per our agreements with Irv Peltier of DCL, the following discussion is pro-vided to complete our comitment regarding verification of core bypass flow
. rate:
Introduction The expected Icakage flows (as defined in the FSAR section 3, pages 3-43 and 3-43a) have been recalculated and updated to reflect current core and system pressure drop information and reported as built dimensions.
Leakage flow is defined as that part of the system flow that does not contact i
the active heat transfer surface. The reactor core flow is the reactor system flow less the leakage flow. There are three major leakage paths plus an addi-tional leakage allowance to account for calculational uncertainties. The three major leakage paths are (1) through the core shroud, (2) through the control rod guide tubes-and ~ instrument tubes, and (3) between all' interfaces separating the inlet and outlet regions.
Su=ary The following tabic shows the breakdown of the updated Icakage calculations:
Path
3f System Flow
- 1) Shroud 1.64
- 2) Control rod guide tubes 6 instrument guide tubes-1.67
- 3) Inlet to outlet interfaces 0.36
~
Total 3.67
>- 1
(
Babcock & Wilcox -
Mr. P. H. Barton Outstanding Compliance Items
'16.D
~2-January 4,1973 Tne 5 be con.4% leakage flow was the original design all servative.
established' leakage flow rate of 3.67% reported aboveT than the
'We expect that this information will resolve the s bj u
ect compliance item.
Very truly yours R. V. Straub RVS/slb~
Project Manager CC:
S. K. Blackley G. X. Baccich W. Faasse R. J. McConnell 1
9 4
e e
G e
6 hh e
3 4
.